IR 05000244/2021010

LLC: NRC Inspection Report 05000244/2021010

ML21155A020
Person / Time
Site:	Ginna
Issue date:	06/07/2021
From:	Glenn Dentel NRC/RGN-I/DORS
To:	Rhoades D Exelon Generation Co
References
IR 2021010
Download: ML21155A020 (8)

Text

June 7, 2021

SUBJECT:

R.E. GINNA NUCLEAR POWER PLANT, LLC - NRC INSPECTION REPORT 05000244/2021010

Dear Mr. Rhoades:

On May 20, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at R.E. Ginna Nuclear Power Plant, LLC and discussed the results of this inspection with Mr. Paul Swift, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Digitally signed by Glenn Glenn T. T. Dentel Date: 2021.06.07 Dentel 10:21:19 -04'00'

Glenn T. Dentel, Chief Engineering Branch 2 Division of Operating Reactor Safety Docket No. 05000244 License No. DPR-18

Enclosure:

As stated

Inspection Report

Docket Number: 05000244 License Number: DPR-18 Report Number: 05000244/2021010 Enterprise Identifier: I-2021-010-0014 Licensee: Exelon Nuclear Facility: R.E. Ginna Nuclear Power Plant, LLC Location: Ontario, New York Inspection Dates: May 03, 2021 to May 20, 2021 Inspectors: M. Patel, Senior Reactor Inspector C. Hobbs, Reactor Inspector B. Pinson, Reactor Inspector Approved By: Glenn T. Dentel, Chief Engineering Branch 2 Division of Operating Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an NRC inspection at R.E. Ginna Nuclear Power Plant, LLC, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

However, all the inspection activities were performed onsite.

REACTOR SAFETY

71111.21N.05 - Fire Protection Team Inspection (FPTI) Structures, Systems, and Components (SSCs) Credited for Fire Prevention, Detection, Suppression, or Post-Fire Safe Shutdown Review (IP Section 03.01)

The inspectors verified that components and/or systems will function as required to support the credited functions stated for each sample. Additional inspection considerations are located in the fire hazards analysis (FHA) or safe shutdown analysis (SSA).

(1) Fire Protection Water Supply System - Fire Pumps and Tank

(2) Chemical and Volume Control System, including Alternate RCS Injection System

(3) Standby Auxiliary Feedwater System

(4) Fire Penetration Seals

Fire Protection Program Administrative Controls (IP Section 03.02) (2 Samples)

The inspectors verified that the selected control or process is implemented in accordance with the licensees current licensing basis. If applicable, ensure that the licensees FPP contains adequate procedures to implement the selected administrative control. Verify that the selected administrative control meets the requirements of all committed industry standards.

(1) Combustible Control Program

(2) Fire Brigade Training, Drills, and Qualifications

Fire Protection Program Changes/Modifications (IP Section 03.03) (1 Sample)

The inspectors verified the following changes to the approved fire protection program do not constitute an adverse effect on the ability to safely shutdown.

(1) ECP-19-000271-209-01-01, Replace S26 Alarm Check Valve and Install new electronic time delay vs. retard chamber to prevent inadvertent fire pump starts

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On May 20, 2021, the inspectors presented the NRC inspection results to Mr. Paul Swift, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21N.05 Corrective Action 4259521,

Documents 4277334,

287990,

4319723,

26202,

4366987,

4385406,

4388167,

4391803,

4404734,

4406238,

4416369

Corrective Action 4424323,

Documents 4424527,

Resulting from 4421635,

Inspection 4424750, PCR

21-01606

Drawings 33013-1230 Alternate RCS Injection System (BDB) P&ID Revision 7

33013-1238 Standby Auxiliary Feedwater (FW) P&ID Revision 44

33013-1265 Auxiliary Control Building Chemical Volume Control Revision 27

System Charging (CVCS), Sheet 2

33013-3131 SAFW and NFPA805 1000KW STANDBY DIESEL Revision 3

GENERATOR SETS

Engineering ECP-12-000459, DDSAFW Project Electrical Design and Installation Revision 1

Changes ESR-11-0050

ESR

ECP-14-000169 Alternate RCS Injection System Revision 000

ECP-19-000271 Replace S26 Alarm Check Valve Revision 001

ECP-21-000006 Extended Diesel Fire Pump Auto Start Test Frequency Revision 000

from Weekly to Monthly

Miscellaneous EPM-FPPR R.E. Ginna Nuclear Power Plant Fire Protection Program Revision 19

GINNA UFSAR Revision 29

Inspection Type Designation Description or Title Revision or

Procedure Date

LR-FWS- Fire Water System Program Revision 9

PROGPLAN

Technical Revision 73

Requirements

Manual for R.E.

Ginna Nuclear

Power Plant

Procedures A-54.7 Fire Protection Tour Revision 039

ATT-18.1 Attachment Alternate RCS Injection / Standby Aux Revision 005

Feedwater

ER-FIRE.0 Control Response to Fire Alarms and Reports Revision 18

ER-FIRE.1 Attachment 1, Shift Technical Advisor (STA) Revision 042

ER-FIRE.1 Attachment 4, Control Operator (CO) Revision 050

ER-FIRE.1 Attachment 8, Long Term DC Power Supply Revision 050

FPS-2 Ginna Station Fire Barrier Penetration Seal Program Revision 9

FPS-3 Fire Barrier Inspection Program Revision 5

FPS-7 Velocity Flush of the Fire Water System completed

04/16/2018

FSG-4 ELAP DC Bus Load Shed / Management Revision 003

OP-AA-102-106 Operator Response Time Program Revision 7

OP-GI-102-106 Operator Response Time Program at Ginna Station Revision 12

STP-O-40.10 Alternate RCS Injection System Flow Test (PCH02, completed

PDB07A, PDB07B) 11/03/2020

STP-O-40.11 Alternate RCS Injection System Portable Diesel Run and completed

Pump Flow Test (PBD04) 10/22/2020

Work Orders C93709945,

C93710744,

C93719069,

C93720739

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